Abstract
The following system studies were performed for the International Thermonuclear Experimental Reactor (ITER) using the Tokamak Engineering Test Reactor Analysis (TETRA) systems code: (1) a study of inductive vs current drive options for ITER, which addresses the cost trade-off of providing increased plasma burn capability inductively by increasing the bore of the ohmic heating (OH) solenoid (resulting in a tokamak with a larger major radius) as opposed to providing plasma current drive via rf or neutral beam injection (NBI); (2) an inboard shield trade study, which addresses the trade-off of using tungsten or stainless steel shielding; and (3) a study of the impact of confinement scaling on ITER parameters, which addresses the sensitivity of various proposed energy confinement time scaling algorithms (Kaye-Goldston, Goldston, T10, JAERI, Rebut) on ITER ignition margin and cost.
Original language | English |
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Pages (from-to) | 605-611 |
Number of pages | 7 |
Journal | Fusion Technology |
Volume | 15 |
Issue number | 2 pt 2A |
DOIs | |
State | Published - 1989 |
Event | Proceedings of the Eighth Topical Meeting on the Technology of Fusion Energy - Salt Lake City, UT, USA Duration: Oct 9 1988 → Oct 13 1988 |